Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water Reactor

SCWR (Supercritical Water Reactor) is one of the promising Generation IV nuclear systems, which has higher thermal power efficiency than current pressurized water reactor. It is necessary to perform the thermal equilibrium and thermal power calculation for the conceptual design and further monitorin...

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Main Authors: Fan Zhang, Dao-gang Lu, Dan-ting Sui, Bo Yuan, Chao Guo
Format: Article
Language:English
Published: Hindawi Limited 2014-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2014/279092
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spelling doaj-a87e314d65d445b7bc60f65ad376a4ec2020-11-25T00:37:06ZengHindawi LimitedScience and Technology of Nuclear Installations1687-60751687-60832014-01-01201410.1155/2014/279092279092Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water ReactorFan Zhang0Dao-gang Lu1Dan-ting Sui2Bo Yuan3Chao Guo4School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaSchool of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaSchool of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaSchool of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaSchool of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaSCWR (Supercritical Water Reactor) is one of the promising Generation IV nuclear systems, which has higher thermal power efficiency than current pressurized water reactor. It is necessary to perform the thermal equilibrium and thermal power calculation for the conceptual design and further monitoring and calibration of the SCWR. One visual software named H-Power was developed to calculate thermal power and its uncertainty of SCWR, in which the advanced IAPWS-IF97 industrial formulation was used to calculate the thermodynamic properties of water and steam. The ISO-5167-4: 2003 standard was incorporated in the code as the basis of orifice plate to compute the flow rate. New heat balance model and uncertainty estimate have also been included in the code. In order to validate H-Power, an assessment was carried out by using data published by US and Qinshan Phase II. The results showed that H-Power was able to estimate the thermal power of SCWR.http://dx.doi.org/10.1155/2014/279092
collection DOAJ
language English
format Article
sources DOAJ
author Fan Zhang
Dao-gang Lu
Dan-ting Sui
Bo Yuan
Chao Guo
spellingShingle Fan Zhang
Dao-gang Lu
Dan-ting Sui
Bo Yuan
Chao Guo
Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water Reactor
Science and Technology of Nuclear Installations
author_facet Fan Zhang
Dao-gang Lu
Dan-ting Sui
Bo Yuan
Chao Guo
author_sort Fan Zhang
title Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water Reactor
title_short Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water Reactor
title_full Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water Reactor
title_fullStr Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water Reactor
title_full_unstemmed Preliminary Development of Thermal Power Calculation Code H-Power for a Supercritical Water Reactor
title_sort preliminary development of thermal power calculation code h-power for a supercritical water reactor
publisher Hindawi Limited
series Science and Technology of Nuclear Installations
issn 1687-6075
1687-6083
publishDate 2014-01-01
description SCWR (Supercritical Water Reactor) is one of the promising Generation IV nuclear systems, which has higher thermal power efficiency than current pressurized water reactor. It is necessary to perform the thermal equilibrium and thermal power calculation for the conceptual design and further monitoring and calibration of the SCWR. One visual software named H-Power was developed to calculate thermal power and its uncertainty of SCWR, in which the advanced IAPWS-IF97 industrial formulation was used to calculate the thermodynamic properties of water and steam. The ISO-5167-4: 2003 standard was incorporated in the code as the basis of orifice plate to compute the flow rate. New heat balance model and uncertainty estimate have also been included in the code. In order to validate H-Power, an assessment was carried out by using data published by US and Qinshan Phase II. The results showed that H-Power was able to estimate the thermal power of SCWR.
url http://dx.doi.org/10.1155/2014/279092
work_keys_str_mv AT fanzhang preliminarydevelopmentofthermalpowercalculationcodehpowerforasupercriticalwaterreactor
AT daoganglu preliminarydevelopmentofthermalpowercalculationcodehpowerforasupercriticalwaterreactor
AT dantingsui preliminarydevelopmentofthermalpowercalculationcodehpowerforasupercriticalwaterreactor
AT boyuan preliminarydevelopmentofthermalpowercalculationcodehpowerforasupercriticalwaterreactor
AT chaoguo preliminarydevelopmentofthermalpowercalculationcodehpowerforasupercriticalwaterreactor
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